Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes

<table class="table-group" width="800px"><tr class="fig-image" id="a"><td><img alt="746467.fig.0022a" src="https://static.hindawi.com/articles/stni/volume-2012/746467/figures/746467.fig.0022a.jpg"/></td></tr><tr class="fig-caption"><td align="center"><table><tr><td><b>(a) </b>Test series 0</td></tr></table></td></tr><tr class="fig-image" id="b"><td><img alt="746467.fig.0022b" src="https://static.hindawi.com/articles/stni/volume-2012/746467/figures/746467.fig.0022b.jpg"/></td></tr><tr class="fig-caption"><td align="center"><table><tr><td><b>(b) </b>Test series 8</td></tr></table></td></tr></table>

<table>DNB Results with different CHF models.</table>

Science and Technology of Nuclear Installations

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Figure 22

Figure 22: Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes 

Figure 22 | Analysis of Void Fraction Distribution and Departure from Nucleate Boiling in Single Subchannel and Bundle Geometries Using Subchannel, System, and Computational Fluid Dynamics Codes 